GB1397723A - Guide structure for control elements - Google Patents

Guide structure for control elements

Info

Publication number
GB1397723A
GB1397723A GB3089873A GB3089873A GB1397723A GB 1397723 A GB1397723 A GB 1397723A GB 3089873 A GB3089873 A GB 3089873A GB 3089873 A GB3089873 A GB 3089873A GB 1397723 A GB1397723 A GB 1397723A
Authority
GB
United Kingdom
Prior art keywords
core
coolant
tubes
control elements
plenum
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
GB3089873A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Combustion Engineering Inc
Original Assignee
Combustion Engineering Inc
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Combustion Engineering Inc filed Critical Combustion Engineering Inc
Publication of GB1397723A publication Critical patent/GB1397723A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

1397723 Controlling reactors; emerging core cooling systems COMBUSTION ENG Inc 28 June 1973 [28 June 1972] 30898/73 Heading G6C A guide structure for aligning fuel assemblies in a pressurized water reactor core, and for guiding a plurality of control elements for telescoping movement within guide channels in the fuel assemblies, comprises two spaced tube sheets 80, 82 rigidly connected by a plurality of hollow tubes 84 which extend between them and supported by a flange 87 of a support barrel 86 on a lip 52 of the reactor vessel 22, hanging within a core barrel 48 which is itself supported by a flange 50. Each of the hollow tubes 84 is in alignment with a guide tube 32 in a fuel assembly. The primary or shutdown control element assemblies 56, 58 each comprise a plurality of high worth control elements 102 gauged together by means of a yoke 96, 98 resectively connected to a drive rod extension 62 by couplings 100. The assembly 56 is 4-fingered and the assembly 58 is 8-fingered. The drive mechanisms for these assemblies are electromagnetic linear motion drive devices which move the control elements 102 in incremental steps into and out of the reactor core. The fine grain control element assemblies 60 each comprise a single low worth control element (104), (Fig. 6, not shown), completely and individually enshrouded above the reactor core by shrouds or tubing 92 coupled by piping 64 through a single nozzle in the vessel head with an hydraulic actuator which maintains the control elements (104) in either a fully inserted or fully retracted position. The water coolant enters the reactor vessel 22 through inlet nozzles (75), (Fig. 1, not shown), and passes down between the vessel 22 and the core barrel 48, then up through the reactor core into an outlet plenum 74, and finally outwardly through openings 168 in the core barrel 48 and outlet nozzles 76. The outlet plenum 74 is a high cross flow region wherein the coolant is turned to pass through the outlet nozzles 76 and the control elements 102, 104 are shielded from the adverse effects of this high cross flow by the tubes 84 each of which enshrouds one of the control elements. The yokes 96, 98 always remain above the upper tube sheet 82 and are thus never subjected to this high cross flow. Protective shrouds 88, 90 for the gauged control element assemblies 56, 58 are provided above the upper tube sheet 82 and serve to prevent outward bowing of the control elements 102 which might otherwise interfere with the effective insertion of adjacent control element assemblies in the event of an emergency. The fuel assemblies have hollow alignment posts 38 in registry with the upper ends of the guide tubes 32 and these posts 38 enter the lower ends of the tubes 84. The guide structure can be adapted to provide an emergency core cooling system which provides sufficient coolant flow to remove the decay heat should a break occur in the normal coolant system. Emergency core coolant is introduced into an inactive plenum 78 above the upper tube sheet 82 and, as shown in Fig. 10, passes into the outlet plenum 74 via pipes 196 to aid in condensing steam which will then fall back as water into the core 26. Tubes 194 similar to the tubes 84 by-pass the plenum 74 and serve to spray the coolant directly on to the fuel assemblies 28 and their fuel elements 30. Coolant also passes through the tubes 84 and into the guide tubes 32 of the fuel assemblies 28, these latter tubes being provided with holes 200 in the lower region of the core 26 whereby the coolant by-passes the plenum 74 and a substantial portion of the core 26. Steam in the outlet plenum 74 is released into the inactive plenum 78 via pipes 198 where it is condensed by the emergency coolant. A system is also described (Fig. 11, not shown) which by using pressurized emergency coolant can overcome any possible steam blockage occurring in the upper region of the core.
GB3089873A 1972-06-28 1973-06-28 Guide structure for control elements Expired GB1397723A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US00266858A US3849257A (en) 1972-06-28 1972-06-28 Guide structure for control elements

Publications (1)

Publication Number Publication Date
GB1397723A true GB1397723A (en) 1975-06-18

Family

ID=23016271

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3089873A Expired GB1397723A (en) 1972-06-28 1973-06-28 Guide structure for control elements

Country Status (7)

Country Link
US (1) US3849257A (en)
JP (1) JPS5347880B2 (en)
CA (1) CA992672A (en)
ES (1) ES416637A1 (en)
FR (1) FR2202339A1 (en)
GB (1) GB1397723A (en)
SE (1) SE384289B (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3023992A1 (en) * 1979-07-02 1981-01-29 Babcock & Wilcox Co BRACKET FOR A CORE REACTOR CONTROL DEVICE

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Publication number Priority date Publication date Assignee Title
DE2310080A1 (en) * 1973-02-28 1974-08-29 Siemens Ag BOILING WATER REACTOR
CA1027679A (en) * 1973-07-31 1978-03-07 Walter E. Desmarchais Emergency core cooling system for a nuclear reactor
US3976834A (en) * 1974-03-25 1976-08-24 Combustion Engineering, Inc. Emergency core cooling injection manifold
AT369179B (en) * 1974-04-10 1982-12-10 Kraftwerk Union Ag DETACHABLE IN A REACTOR PRESSURE TANK
US4050986A (en) * 1974-09-13 1977-09-27 The United States Of America As Represented By The United States Energy Research And Development Administration Nuclear reactor I
JPS51140090A (en) * 1975-05-30 1976-12-02 Hitachi Ltd Fuel aggregate
US4073684A (en) * 1976-09-27 1978-02-14 Combustion Engineering, Inc. Releasable extension shaft coupling
DE3008442A1 (en) * 1980-03-05 1981-09-10 Kraftwerk Union AG, 4330 Mülheim FUEL ELEMENT FOR A CORE REACTOR
DE3009937A1 (en) * 1980-03-14 1981-09-24 Kraftwerk Union AG, 4330 Mülheim High converter reactor in pressurised water reactor vessel - occupies lower core zone and has absorber rods with common drive
US4832899A (en) * 1980-12-16 1989-05-23 Westinghouse Electric Corp. Mechanical spectral shift reactor
FR2501892B1 (en) * 1981-03-13 1985-10-25 Framatome Sa NUCLEAR REACTOR WITH DEVICE FOR GUIDING THE CONTROL CLUSTERS
FR2516691A1 (en) * 1981-11-13 1983-05-20 Framatome Sa DEVICE FOR GUIDING A NUCLEAR REACTOR CONTROL CLUSTER
JPS59151132U (en) * 1983-03-29 1984-10-09 明星電気株式会社 pressure gauge
US4659539A (en) * 1983-04-29 1987-04-21 Westinghouse Electric Corp. Nuclear reactor
US4716013A (en) * 1983-04-29 1987-12-29 Westinghouse Electric Corp. Nuclear reactor
FR2547100B1 (en) * 1983-06-03 1985-08-30 Framatome Sa GUIDANCE DEVICE FOR NUCLEAR REACTOR CONTROL CLUSTERS
JPS62152704A (en) * 1985-12-27 1987-07-07 株式会社 湊組 Manufacture of mortar lining steel pipe
JPS62152705A (en) * 1985-12-27 1987-07-07 技術資源開発株式会社 Steel-pipe mortar lining device
FR2595501B1 (en) * 1986-03-07 1988-06-10 Framatome Sa INTERNAL EQUIPMENT OF NUCLEAR REACTORS WITH EXTENDED TANK
US4759904A (en) * 1986-04-04 1988-07-26 Westinghouse Electric Corp. Pressurized water reactor having improved calandria assembly
US4902468A (en) * 1987-10-21 1990-02-20 Westinghouse Electric Corp. Control rod support having planar wear surfaces
FR2627321B1 (en) * 1988-02-11 1992-08-14 Framatome Sa SUPERIOR INTERNAL EQUIPMENT OF NUCLEAR REACTOR PROVIDED WITH A FLOW SEPARATION DEVICE
JPH01301207A (en) * 1988-05-30 1989-12-05 Kubota Ltd Lining of inner face of pipe
FR2635906B1 (en) * 1988-08-25 1990-11-23 Framatome Sa INSTRUMENTATION DEVICE FOR THE HEART OF A PRESSURIZED WATER NUCLEAR REACTOR AND METHOD AND DEVICE FOR EXTRACTING AND PLACING THE INSTRUMENTATION DEVICE
US5024808A (en) * 1988-10-14 1991-06-18 Westinghouse Electric Corp. Combined support column and guide tube for use in a nuclear reactor
US4937039A (en) * 1989-01-17 1990-06-26 Westinghouse Electric Corp. Four pin mounting system for nuclear reactor control rod guide tubes
US5488643A (en) * 1994-05-11 1996-01-30 Combustion Engineering, Inc. Method and apparatus for supporting a shroud in a nuclear reactor
US8483347B2 (en) * 2007-04-10 2013-07-09 Westinghouse Electric Company Llc Upper internals arrangement for a pressurized water reactor
PL2143996T3 (en) * 2008-02-19 2013-12-31 Balcke Duerr Gmbh Collector for a high pressure device of a steam power array
US8929505B2 (en) * 2009-08-28 2015-01-06 Terrapower, Llc Nuclear fission reactor, vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system
US20110150167A1 (en) * 2009-08-28 2011-06-23 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system
US9269462B2 (en) * 2009-08-28 2016-02-23 Terrapower, Llc Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system
CN102598146B (en) * 2009-08-28 2015-04-01 泰拉能源有限责任公司 Method for assembling air-permeable nuclear fission fuel module
US8712005B2 (en) * 2009-08-28 2014-04-29 Invention Science Fund I, Llc Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system
US8488734B2 (en) * 2009-08-28 2013-07-16 The Invention Science Fund I, Llc Nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system
US11935663B2 (en) 2012-05-21 2024-03-19 Smr Inventec, Llc Control rod drive system for nuclear reactor
US9496057B2 (en) 2012-08-06 2016-11-15 Smr Inventec, Llc Fail-safe control rod drive system for nuclear reactor

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GB552899A (en) * 1941-10-24 1943-04-29 Leonard Shakesby Improvements in or relating to joints between pipes and fuel containers
US2508655A (en) * 1945-07-23 1950-05-23 T & M Mfg Company Clamping connector
US3212979A (en) * 1961-04-18 1965-10-19 Westinghouse Electric Corp Core support structure
BE620146A (en) * 1961-08-01 1900-01-01
GB1112346A (en) * 1963-12-02 1968-05-01 Atomic Energy Authority Uk Improvements relating to nuclear reactors
GB1112946A (en) * 1965-08-10 1968-05-08 Atomic Energy Authority Uk Improvements relating to nuclear reactors
US3481832A (en) * 1967-04-14 1969-12-02 Combustion Eng Nuclear reactor core and control element arrangement
US3595748A (en) * 1968-01-24 1971-07-27 Westinghouse Electric Corp Nuclear reactor control device
US3607629A (en) * 1968-01-24 1971-09-21 Westinghouse Electric Corp Drive mechanism for control elements
DE1764577B1 (en) * 1968-06-28 1971-05-06 Siemens Ag CORE REACTOR CONTROL ROD DEVICE
US3604746A (en) * 1968-11-20 1971-09-14 Combustion Eng Nuclear reactor control element gripper and drive apparatus

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3023992A1 (en) * 1979-07-02 1981-01-29 Babcock & Wilcox Co BRACKET FOR A CORE REACTOR CONTROL DEVICE

Also Published As

Publication number Publication date
DE2331355A1 (en) 1974-01-10
JPS4943096A (en) 1974-04-23
US3849257A (en) 1974-11-19
JPS5347880B2 (en) 1978-12-23
SE384289B (en) 1976-04-26
CA992672A (en) 1976-07-06
DE2331355B2 (en) 1975-11-13
ES416637A1 (en) 1976-12-01
FR2202339A1 (en) 1974-05-03

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee